Scaling of two-phase flow regimes in a rod bundle with Freon
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:5874374
A fundamental requirement of Freon modeling is that the same void fraction and spatial phase distribution will exist in the Freon model as in the steam/water system being simulated. It is shown that this requirement is satisfied by comparing flow regime transitions observed in high-pressure steam/water with transitions observed in the half-scale Freon four-rod test. It is also demonstrated through predictions of a two-fluid model for a one-half geometric scale factor that within each flow regime, a similar slip ratio (vapor-to-liquid-velocity ratio) exists for the Freon and water systems.
- OSTI ID:
- 5874374
- Report Number(s):
- CONF-901101--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 62
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCURACY
BOILING
BUBBLES
BWR TYPE REACTORS
DRAG
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FREONS
HALOGENATED ALIPHATIC HYDROCARBONS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MATHEMATICAL MODELS
MECHANICS
ONE-DIMENSIONAL CALCULATIONS
ORGANIC COMPOUNDS
ORGANIC HALOGEN COMPOUNDS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
ROD BUNDLES
SAFETY
SCALING LAWS
SIMULATION
SPACE DEPENDENCE
STEAM
TEST FACILITIES
TWO-PHASE FLOW
VAPOR CONDENSATION
VOID FRACTION
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCURACY
BOILING
BUBBLES
BWR TYPE REACTORS
DRAG
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FREONS
HALOGENATED ALIPHATIC HYDROCARBONS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MATHEMATICAL MODELS
MECHANICS
ONE-DIMENSIONAL CALCULATIONS
ORGANIC COMPOUNDS
ORGANIC HALOGEN COMPOUNDS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
ROD BUNDLES
SAFETY
SCALING LAWS
SIMULATION
SPACE DEPENDENCE
STEAM
TEST FACILITIES
TWO-PHASE FLOW
VAPOR CONDENSATION
VOID FRACTION
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS